Welcome to Prof. Lee’s lab!

Nuclear Fuel Cycle and Radiochemistry Laboratory (NURAD Lab.) conducts in-depth research on topics that are important in the back-end nuclear fuel cycle, such as safe and efficient management/treatment of spent nuclear fuel, reliable safety assessment of waste repository, decommission/decontamination/remediation technologies regarding the nuclear facility, and provides a bridgehead for various fields of the nuclear industry by cultivating expertise on relevant issues.

The issue of spent nuclear fuel and radioactive waste, which inevitably arise from the continuous use of nuclear energy, has been cited as an important task to be resolved soon. From the perspective of geologic disposal, the migration/retardation behavior of radionuclides in the natural groundwater system is highly influenced by various geochemical factors such as solubility, sorption/adsorption, chemical complexation, oxidation/reduction, etc. Therefore, we are focusing on the quantification of those geochemical factors to find ways to resolve relevant issues, by using various analytical methods.

The study of reuse of spent nuclear fuel as well as decontamination/decommission of a nuclear facility is also widely seen as major issues in the back-end nuclear fuel cycle. From this point of view, we are expanding our interest in relevant research areas such as molten-salt chemistry, contaminant evaluation, assessment of ecological restoration, development of adsorbent materials, and so on.

We are recruiting undergraduate and graduate students who have an interest in the back-end nuclear fuel cycle and nuclear waste management technologies.

Thank you for your interest!

Radioactive Waste Disposal (방사성폐기물 처분)

Migration/retardation behavior of radioisotopes in natural groundwater system

Safety assessment of radioactive waste repository

 

Actinide and Radiochemistry (악티나이드 및 방사화학)

Aqueous solubility and complexation reactions of lanthanides and actinides

Redox behavior of An(III/IV/V/VI) in aqueous medium

Chemical thermodynamic data (formation constants, solubility products, etc.)

 

Decontamination/Remediation (제염 및 오염저감)

Sorption/adsorption characteristics of various radioisotopes

Development of adsorbent for removal of contaminants

J.-Y. Lee, D. Fellhauer, X. Gaona, E. Yalcintas, M. Altmaier
Solubility and stability of liebigite, Ca2UO2(CO3)3·10H2O(cr), in dilute to concentrated NaCl and NaClO4 solutions at T = 22–80 °C
Applied Geochemistry, 2019, Vol. 111, No. 0, pp. 0~ 0

D. H. Kam, Y. H. Jeong, S.-M. Choi, J.-I. Yun, J. H. Lee, T. Lee, M. S. Lee, I.-K. Jung, J.-W. Jang, Y. Sihn, T.-H. Kim, J.-K. Lee, S.-H. Kang, J.-Y. Lee
A novel approach for critical heat flux enhancement during severe accident mitigation with removal of radioactive materials from the coolant
Nuclear Engineering and Design, 2020, Vol. 365, No. 0, pp. 110715~ 0

Y. Jo, J.-Y. Lee, J.-I. Yun
Adsorption of uranyl tricarbonate and calcium uranyl carbonate onto γ-alumina
Applied Geochemistry, 2018, Vol. 94, No. 28, pp. 0~ 0